US2998370A - Nuclear reactors - Google Patents

Nuclear reactors Download PDF

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Publication number
US2998370A
US2998370A US686203A US68620357A US2998370A US 2998370 A US2998370 A US 2998370A US 686203 A US686203 A US 686203A US 68620357 A US68620357 A US 68620357A US 2998370 A US2998370 A US 2998370A
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United States
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pile
blocks
layer
base
base member
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US686203A
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Gaunt Ian Alexander Butler
Mitchell Keith James
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General Electric Co PLC
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General Electric Co PLC
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
    • G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to nuclear reactors and particularly to nuclear reactors having a core including units of moderating material assembled into a pile and resting on a base support or raft.
  • a base support or raft of the type herein envisaged may arise in a number of ways, but principally in the case where the core is required to be supported within an enclosing vessel generally spherical or part-spherical in shape without unduly straining the vessel.
  • the base support or raft may adequately carry the weight of the core together with any additional load such as the weight of fuel elements contained therein, it is generally necessary to construct the support of a different material 'from that of the core.
  • graphitic carbon moderating material may be used and the base support or raft may be made of steel. Since steel has a considerably higher coefficient of thermal expansion than the 'graphitic carbon used as moderating material, operation of the nuclear reactor may cause separation of the base units of the core from one another with the possibility of serious distortion of the pile, since a single pile may be composed of several thousand units of moderating material.
  • the units of the pile are rigidly bound together, for example by circumferential restraints of the garter type, the lowest restraints have to withstand the frictional forces caused by the sliding of the carbon over the steel. These forces may be considerable, particularly in the dry atmosphere of a gas-cooled reactor.
  • the units are arranged in vertical columns held together at the top but free to move radially outward at the bottom with the base support or raft.
  • the top ends of the columns form a cap for the pile as a whole, while their lower ends may be individually attached to the base support or raft at regular intervals so as to breathe, or move regularly to and from each other during thermal cycling of the reactor, such breathing being normally arranged to vary in a substantially linear fashion from a maximum at the base of the pile to a minimum at the cap.
  • the units forming a single column may be kept in register with one another by keys and mating recesses or grooves machined intothe end faces of the units, which may be of the kind described in the specification accompanying United States patent application Serial No. 726,887 filed April 7, 1958 by Ian Alexander Butler Gaunt for Graphite Moderator Units, now abandoned, corresponding to British patent application No. 11813/57 dated October 4, 1957
  • Such an arrangement ensures flexibility, since the number of units will generally be large enough to provide a correspondingly large number of joints in each column.
  • the top ends of the columns may then be rigidly held together by garter restraints having the same coelficient of thermal expansion as the moderating material, while the lower end of each column is attached to the base support or raft by spigot or the like means.
  • such restraint is provided by members attached to substantially vertical bars or channels, each bar or channel being pivotally attached at one end to the base support or raft, or to a base supporting structure arranged to expand therewith, and at the other end to the top of the pile.
  • the bars or channels pivot about their attachments to the raft or base supporting structure due to differential expansion between the latter and the moderating material.
  • the members may be attached to the bars or channels through legs which may be adjusted so as to exert a slight locating force on the pile through the members. These legs may be pivoted at both ends to permit the bars or channels to expand vertically at a greater rate than the moderating material.
  • One advantage of the arrangement according to the invention is that, since the upper part of the core of a reactor incorporating the arrangement will normally run at a higher temperature than the lower, the differential thermal expansion of the core itself will tend to a considerable extent to offset the overall expansion of the lower part due to the opening out of the columns. Thus the core may be less distorted during operation than if it had been tightly constrained throughout and supported for example on ball or roller bearings.
  • FIGS l to 8 of the accompanying drawings show parts of the reactor core, which is supported inside a pressure vessel in such a way as to allow coolant gas such as carbon dioxide under pressure to pass up through passages or ducts in the core, abstracting heat from fuel elements supported therein and being subsequently discharged from the top of the core into heat exchangers, where the heat given up by the gas is used to generate steam for use in turbo-alternator plant.
  • coolant gas such as carbon dioxide under pressure
  • FIGURE 1 shows a part sectional elevation of the reactor core.
  • FIGURE 2 shows a fragmentary plan of the core.
  • FIGURE 3 shows a view on the line III-Ill of FIG- URE l.
  • FIGURE 4 shows a section on the line IV-IV of FIGURE 1.
  • FIGURE 5 shows a section on the line VV of FIG- URE l.
  • FIGURE 6 shows a section on the line VI-VI of FIGURE 3.
  • FIGURE 7 shows a detail of the manner in which the moderator columns are spigotted into the base support or raft.
  • FIGURE 8 shows a detail of the gas seal between the periphery of the moderator structure and the base support or raft.
  • the reactor core includes units of graphite moderating material in the form of bricks such as l or tiles such as 2 assembled into a pile 3.
  • the pile has the shape of a twenty-eight sided polygon in cross-section, and has substantially vertical sides. It is composed of the moderator proper, situated in the middle of the pile 3, and a series of units placed around the moderator and constituting a neutron reflector.
  • the boundary between moderator and reflector is indicated by the heavy dividing line 4 in FIGURE 2 and reflector layers are also provided at the top and bottom of the moderator.
  • the outermost columns of moderator units are composed of bricks 1 not separated by tiles 2 except in the case of the innermost reflector column, which is formed of bricks separated by a single layer of tiles having twice the thickness of the moderator tiles 2.
  • the moderator itself is composed of bricks 1 separated by two layers of tiles 2.
  • the reason for this construction lies in the growth under irradiation, or Wigner growth, of the graphite moderator.
  • the bricks 1. in a given moderator layer are separated from each other and only the tiles 2 are contiguous in one lateral direction.
  • Wigner growth is considerably greater in a direction at right angles to the grain of the graphite than parallel to the grain and advantage is taken of this fact in known fashion by arranging that one layer of tiles abuts in a lateral direction corresponding to the direction of grain of the tiles, while the other layer of tiles abuts in a direction at right angles to the first layer.
  • the direction of the grain of the bricks themselves is arranged to be vertical.
  • each abutting face is of substantially square cross-section, with upstanding keys on two opposite edges and mating recesses on the remaining two edges.
  • a central orifice is bored through each unit, such orifices together forming a continuous duct or channel down through the moderator from top to bottom.
  • Additional ducts or channels, passing from the top of the pile through the moderator, are also provided for control rods.
  • the general arrangement of the pile units which is substantially conventional in character, thus provides a series of moderator columns composed of units keyed to one another, the number'of units being sufliciently large to ensure some degree of flexibility of the column. These columns are arranged adjacent each other and in fact abut through the tiles 2.
  • the above arrangement is slightly modified at different 7 parts of the pile; for example, the top two pairs of tile substantially rigid cap for the pile; the outermost row of bricks on this layer is omitted, to give suflicient clearance from the reactor shell or pressure vessel 5.
  • vertical ducts or channels are not provided in the side reflector; and not all the reflector units are of substantially square section since it is necessary to transfer from the square lattice pattern to the twenty-eight sided shape. Only the square-sectioned bricks are keyed to one another. Other reflector bricks are merely laid end to end and no allowance is made for Wigner growth since the flux level of irradiation is small and it is desirable to keep the density of the reflector as high as possible.
  • Thermocouple cables are laid in the lower of each pair of tile layers,
  • the whole core of the reactor comprising the pile and fuel elements and other apparatus contained therein, rests on a base support in the form of a raft.
  • This raft is composed of a number of support plates 6 laid on a grid 7.
  • the support plates 6 are jacked and levelled in position to form a true surface for the bottom (reflector) layer of the pile.
  • the invention provides that each reflector brick 8 (FIGURE 7) of this bottom layer, which brick 8 forms the lower end of a column extending to the top of the pile, is individually attached to a support plate 6; this attachment is effected both by the Weight of the column and by a spigot 9 which, as shown, may also have a tube 10 fixed into it for charging and discharging fuel elements.
  • the spigots 9 are a loose fit in holes in the support plates 6 and are accurately spaced from each other by means of intermediate spacers so as to form an accurate register into which the reflector bricks 8 fit at regular intervals by means of a counter-bore in the lower ends of the vertical ducts or channels in the bricks.
  • a counter-bore provided in one end of the brick of sufficient depth to accept the end of the spigot 9; the outermost layer of these bricks is laid horizontally to accept the weight of the non-square section packing bricks.
  • the raft composed of the support plates 6 will expand.
  • the support plates 6 are made of steel, which has a considerably higher coeificient of thermal expansion than the graphite moderating material.
  • Alternative solutions of this problem have already been discussed and their limitations defined; the present invention provides that the base of the pile expands radially outward at the same rate as the raft while the temperature of the pile is increasing. This is elfected by the spigoting of the graphite directly into the support plates 6, and in consequence the pile opens out at the base, the individual columns of units becoming separated at the bottom by reason of the greater expansion of the steel.
  • top ends of the columns are rigidly held together to form a cap for the pile; the following description outlines the type of restraint used for this purpose, and also the restraint arrangement employed to ensure that the movement of the columns to and from each other during thermal cycling varies substantially linearly from a maximum at the base of the pile to a minimum at the cap. In order that this should happen, the restraint arrangement must move at the base at the same rate as the steel and at the top at the same rate as the graphite.
  • each hinged member is hinged at points 12 to its neighbours and to members 13 of the beam type constituting corner restraints for the pile cap.
  • corner restraints 13 are fitted at the junction of each layer of reflector bricks and form hands across each corner A of the pile, holding the structure together.
  • an uncompensated garter-type restraint 14 is provided. This is set at a greater radius than the compensated restraint 11 and forms, in effect, a parallel linkage therewith.
  • the units of moderating material are restrained first of all by the compensated restraints 11 until the pile cap is properly located, when the uncompensated restraints 14 are tight ened down through screwed links 15.
  • the uncompensated restraints 14 expand thermally to a greater extent than the compensated restraints 11.
  • the structure relaxes slightly to an extent determined by the degree of initial tension in the uncompensated restraints 14, which then hold the cap of the structure together.
  • Slightly modified corner restraints 16 are used in connection with the second layer of bricks from the top of the pile;
  • FIGURES 4 and show details of the modified corner restraint members, which are fitted with radial extensions 17 to which rounded end pieces 18 are secured.
  • Each end piece 18 is located between buffers 19 adjustably attached through brackets 20, 21 to a reactor shell 5.
  • These extensions 17 form rotational restraints acting so as to prevent the top of the pile from twisting.
  • substantially vertical bars or channels 22 of steel are attached through legs 23 to the members 16 forming the corner restraints.
  • Each leg 23 is pivoted at its ends as shown at 24 so that the attachmerit to both bar 22 and corner restraint member 16 is pivotal and, due to the shape of the pivot pins, capable of accommodating small distortions.
  • the vertical channels 22 are tied rigidly together in pairs by means of bolted-on strutting 25.
  • the channels 22 and strutting 25 are of steel and accordingly expand to a greater extent than the corner restraint members 16, which expand with the graphite moderating structure.
  • the pivoting 24 is such as amply to accommodate this differential expansion.
  • each of the legs 23 below the top layer, which locates the top of the pairs of channels 22, is also adjustable longitudinally. Such longitudinal adjustment may be made by means of screws 26 and abutting clamping flanges 27.
  • the pairs of channels 22 are pivotally attached at their lower ends 23 to the base supporting structure 29.
  • This supporting structure 29 forms an extension of the grid 7 in the form of an imperforate annular plate to which the shell 5 is welded, the inner rim of the annulus being attached to a vertical kerb 30 against which the raft formed by the support plates 6 is arranged to abut by means of locating screws (not shown).
  • This base supporting structure 29, which is also of steel, is thus 6 arranged to expand with the raft when the temperature of the pile increases.
  • the effect of an increase in temperature of the pile upon the channels 22 is to cause them to pivot at their lower ends 28 due to the differential expansion between the steel support plates 6, together with the supporting structure 29, and the graphite moderating material of the pilecap.
  • the lower and adjustable legs 23 are initially set to exert a slight locating force on the pile through the corner restraint members 13, and their pivoted attachment permits the channels 22 to expand vertically at a greater rate than the graphite, while keeping the corner restraints in position.
  • the system of channels 22, legs 23 and corner restraints 13 or 16 therefore forms a restraint arrangement which allows the individual columns of graphite units to breathe, or move regularly to and from each other during thermal cycling, and encourages such breathing to vary as far as possible linearly from a maximum at the base of the pile where the columns are spigotted into the raft to a minimum at the top cap of the pile.
  • the top two pairs of tile layers are composed of tiles whose grain is vertical in direction; the reason for this is that the coefiicient of thermal expansion of the lower of these two pairs of tile layers is thereby kept equal to that of the top (reflector) layer of bricks, since the expansion of graphite under heat varies with the direction of the grain and the top reflector is, in this example, of the same material as the tiles.
  • the temperature difference across these two layers of bricks and tiles being only of the order of 10
  • the cap which they form for the pile under the influence of the garter restraints 11 expands radially approximately as a Whole.
  • This top cap is in addition prevented from rotating or moving sideways by the extensions 17 on the corner restraints 16.
  • FIGURE 8 shows how the gas seal is provided between a horizontal reflector brick 31 and support plate 6.
  • a plate 32- is welded to the kerb 30 and rests on the support plate 6.
  • the seal is made between the plate 32 and brick 31 and consists of a continuous U-shaped stainless steel piece 33 held down by a bolted bar 34 which acts as a clamp holding the plates 32 and 6 together.
  • the U-shaped piece 33 is arranged so that the gas pressure will tend to open it up against the brick 31 and thus tighten the seal.
  • An additional gas seal is necessary to prevent leakage of gas up between the graphite columns during breathing when the columns are separated, and this may take the form of a thin sheet of mild steel laid on the support plates 6 so as to form a top skin to the raft, or a number of thin sheets each of the same area as a support plate 6 and placed between the centres of adjacent support plates so as to overlap the gaps between them.
  • a reactor of the kind described in the above example may be designed to run at a temperature of approximately 200 C. at the base of the pile and 400 C. at the top. Then differential expansion of the core of the reactor will act to diminish the difference in expansion of the top and bottom of the pile due to the fact that the bottom of the pile moves with the steel raft.
  • this raft may be 2 /2 times as great as graphite, it has been estimated in one construction that the radial expansion of the steel raft is 0.68" while that of the graphite at the top of the pile is 0.58".
  • the graphite at the top thus expands nearly as fast as the steel at the bottom, and the whole structure remains substantially undistorted during operation.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coefficient of thermal expansion greater than that of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, and garter restraining means, said garter restraining means being arranged to clamp together the blocks in a said layer near the top of the assembly and being adapted to have substantially the same coefiicient of thermal expansion as the moderating material, the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move with thermal movement of that part of the base member with which it is associated.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coefiicient of thermal expansion greater than that of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, clamping means, said clamping means being adapted to clamp together the blocks in a said layer near the top of the assembly, and intermediate restraining means, said intermediate restraining means being adapted to restrain a layer of blocks intermediate between the bottom layer and said clamped layer, means being provided which are adapted to support said intermediate restraining means in relation to said base member, and the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move with thermal movement of that part of the base member with which it is associated.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coeflicient of thermal expansion greater than that of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, clamping means, said clamping means being adapted to clamp together the blocks in a said layer near the top of the assembly, and intermediate restraining means, said intermediate restraining means being adapted to restrain a layer of blocks intermediate between the bottom layer and said clamped layer, and a plurality of substantially vertical members, each said vertical member being pivotally mounted at one part thereof in relation to said base member and at another part thereof in relation to said intermediate restraining means, and the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move with thermal movement of that part of the base member with which it is associated.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coeificient of thermal expansion greater thanthat of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, clamping means, said clamping means being adapted to clamp together the blocks in a said layer near the top of the assembly, a plurality of intet lmdiate re 8 straining means, each said intermediate restraining means being adapted to restrain one of the layers of blocks intermediate between the bottom layer and said clamped layer, a plurality of substantially vertical members, each said vertical member being pivotally mounted at one end thereof in relation to said base member and also at intermediate parts in relation to each said intermediate restraining means, and the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move with thermal movement of that part of the base member with which it is associated.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coefiicient of thermal expansion greater than that of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, and clamping means, said clamping means being adapted to clamp together the blocks in a said layer near the top of the assembly, the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move with thermal movement of that part of the base member with which it is associated, and a containment vessel for said base member and said block assembly and comprising at least one rotational restraint, said rotational restraint being adapted to interact between said vessel and said clamping means to limit twisting movement of said block assembly.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coeificient of thermal expansion greater than that of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, clamping means, said clamping means being adapted to clamp together the blocks in a said layer near the top of the assembly, and intermediate restraining means, said intermediate restraining means being adapted to restrain a layer of blocks intermediate between the bottom layer and said clamped layer, and the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move with thermal movement of that part of the base member with which it is associated, and a containment vessel for said base member and said block assembly and comprising at least one rotational restraint, said rotational restraint being adapted to interact between said vessel and said clamping means to limit twisting movement of said block assembly.
  • a core arrangement for a nuclear reactor comprising blocks of moderating material and a base supporting member of material having a coe'flicient of thermal expansion greater than that of the moderating material, said blocks being assembled in layers and in a plurality of substantially vertical columns in juxtaposition upon said base member, clamping means, said clamping means being adapted to clamp together the blocks in a said layer near the top of the assembly, and intermediate restraining means, said intermediate restraining means being adapted to restrain a layer of blocks intermediate between the bottom layer and said clamped layer, and the blocks in each column below said clamped layer being arranged so that the bottom of each column is free to move 2,838,451 Lon-g et a1 June 10, 1958 with thermal movement of that part of the base member 2,852,457 Long et a1 Sept.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
US686203A 1956-09-27 1957-09-25 Nuclear reactors Expired - Lifetime US2998370A (en)

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GB29606/56A GB837608A (en) 1956-09-27 1956-09-27 Improvements in or relating to nuclear reactors

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BE (1) BE561181A (US20090158533A1-20090625-C00001.png)
DE (1) DE1054604B (US20090158533A1-20090625-C00001.png)
FR (1) FR1189218A (US20090158533A1-20090625-C00001.png)
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Cited By (19)

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US3116214A (en) * 1961-05-19 1963-12-31 Bill L Greenstreet Reactor moderator structure
US3119746A (en) * 1957-11-09 1964-01-28 Commissariat Energie Atomique Devices for supporting at least the solid moderator of a nuclear reactor having vertical channels
US3124514A (en) * 1964-03-10 koutz etal
US3149047A (en) * 1961-07-11 1964-09-15 Arthur P Fraas Resilient moderator structure for neutronic reactors
US3206374A (en) * 1957-11-08 1965-09-14 Commissariat Energie Atomique Belt restraint system for moderator-reflector structure of a nuclear reactor
US3208914A (en) * 1961-01-05 1965-09-28 Allis Chalmers Mfg Co Nuclear reactor with improved core arrangement facilitating loading and unloading of fuel assemblies and control rod assemblies
US3252868A (en) * 1959-06-03 1966-05-24 Philips Corp Fuel element for use in nuclear reactors
US3629070A (en) * 1969-06-09 1971-12-21 Atomic Energy Commission Temperature-activated reactor core clamp
US3708393A (en) * 1970-12-01 1973-01-02 Atomic Energy Commission Radial restraint mechanism for reactor core
US3755078A (en) * 1971-12-27 1973-08-28 North American Rockwell Segmented hydraulic core clamp
US3987860A (en) * 1969-05-09 1976-10-26 The Babcock & Wilcox Company Nuclear reactor core stabilizing arrangement
US4199403A (en) * 1977-11-21 1980-04-22 Combustion Engineering, Inc. Seismic core shroud
US4629601A (en) * 1984-01-09 1986-12-16 Westinghouse Electric Corp. Stirrup-type support structure for nuclear power plant pressurizer valves
US5588031A (en) * 1994-10-27 1996-12-24 Westinghouse Electric Corporation Apparatus for reinforcing a reactor vessel core shroud
US5687206A (en) * 1996-03-15 1997-11-11 Mpr Associates, Inc. Method of replacing a boiling water reactor core shroud
US5828713A (en) * 1996-10-15 1998-10-27 Mpr Associates, Inc. Replacement core shroud assembly for a boiling water reactor
WO2006018782A1 (en) * 2004-08-13 2006-02-23 Pebble Bed Modular Reactor (Proprietary) Limited Nuclear reactor
JP2013024619A (ja) * 2011-07-19 2013-02-04 Fuji Electric Co Ltd 高温ガス炉の炉心拘束機構
RU208108U1 (ru) * 2021-08-03 2021-12-02 Акционерное общество "Научно-исследовательский центр "Строительство", АО "НИЦ "Строительство" Защитная оболочка ядерного реактора

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GB890520A (en) * 1959-06-03 1962-02-28 Babcock & Wilcox Ltd Improvements in nuclear reactors and in restraint garters therefor
DE1220943B (de) * 1959-06-16 1966-07-14 Atomic Energy Authority Uk Abstuetzung fuer die Kernanordnung eines Atomkernreaktors
NL129679C (US20090158533A1-20090625-C00001.png) * 1960-03-11
GB908305A (en) * 1960-07-01 1962-10-17 Atomic Energy Authority Uk Improvements in or relating to nuclear reactors
GB918644A (en) * 1960-11-13 1963-02-13 Atomic Energy Authority Uk Improvements relating to thermal nuclear reactors
NL284378A (US20090158533A1-20090625-C00001.png) * 1961-10-26
DE1237231B (de) * 1963-02-08 1967-03-23 Kernforschung Mit Beschraenkte Spanneinrichtung fuer die Spalt- und Brutzone eines Atomkernreaktors

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US2838451A (en) * 1954-11-13 1958-06-10 Long Everett Gas cooled nuclear reactors
US2852457A (en) * 1955-06-30 1958-09-16 Long Everett Nuclear reactors

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US3124514A (en) * 1964-03-10 koutz etal
US3206374A (en) * 1957-11-08 1965-09-14 Commissariat Energie Atomique Belt restraint system for moderator-reflector structure of a nuclear reactor
US3119746A (en) * 1957-11-09 1964-01-28 Commissariat Energie Atomique Devices for supporting at least the solid moderator of a nuclear reactor having vertical channels
US3252868A (en) * 1959-06-03 1966-05-24 Philips Corp Fuel element for use in nuclear reactors
US3208914A (en) * 1961-01-05 1965-09-28 Allis Chalmers Mfg Co Nuclear reactor with improved core arrangement facilitating loading and unloading of fuel assemblies and control rod assemblies
US3116214A (en) * 1961-05-19 1963-12-31 Bill L Greenstreet Reactor moderator structure
US3149047A (en) * 1961-07-11 1964-09-15 Arthur P Fraas Resilient moderator structure for neutronic reactors
US3987860A (en) * 1969-05-09 1976-10-26 The Babcock & Wilcox Company Nuclear reactor core stabilizing arrangement
US3629070A (en) * 1969-06-09 1971-12-21 Atomic Energy Commission Temperature-activated reactor core clamp
US3708393A (en) * 1970-12-01 1973-01-02 Atomic Energy Commission Radial restraint mechanism for reactor core
US3755078A (en) * 1971-12-27 1973-08-28 North American Rockwell Segmented hydraulic core clamp
US4199403A (en) * 1977-11-21 1980-04-22 Combustion Engineering, Inc. Seismic core shroud
US4629601A (en) * 1984-01-09 1986-12-16 Westinghouse Electric Corp. Stirrup-type support structure for nuclear power plant pressurizer valves
US5588031A (en) * 1994-10-27 1996-12-24 Westinghouse Electric Corporation Apparatus for reinforcing a reactor vessel core shroud
US5687206A (en) * 1996-03-15 1997-11-11 Mpr Associates, Inc. Method of replacing a boiling water reactor core shroud
US5828713A (en) * 1996-10-15 1998-10-27 Mpr Associates, Inc. Replacement core shroud assembly for a boiling water reactor
WO2006018782A1 (en) * 2004-08-13 2006-02-23 Pebble Bed Modular Reactor (Proprietary) Limited Nuclear reactor
US20070253521A1 (en) * 2004-08-13 2007-11-01 Mitchell Mark N Nuclear Reactor
JP2008510133A (ja) * 2004-08-13 2008-04-03 ペブル ベッド モデュラー リアクター （プロプライエタリー） リミテッド 原子炉
JP2013024619A (ja) * 2011-07-19 2013-02-04 Fuji Electric Co Ltd 高温ガス炉の炉心拘束機構
RU208108U1 (ru) * 2021-08-03 2021-12-02 Акционерное общество "Научно-исследовательский центр "Строительство", АО "НИЦ "Строительство" Защитная оболочка ядерного реактора

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FR1189218A (fr) 1959-10-01
GB837608A (en) 1960-06-15
BE561181A (US20090158533A1-20090625-C00001.png) 1900-01-01
DE1054604B (de) 1959-04-09
NL102745C (US20090158533A1-20090625-C00001.png) 1900-01-01

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